Segmented full-automatic control method and system for high-temperature gas cooled reactor unit

Abstract

The invention relates to the technical field of high-temperature gas cooled reactor power automatic control, and discloses a segmented full-automatic control method and system for a high-temperature gas cooled reactor unit, and the method comprises the steps: monitoring the characteristics of a reactor core and the steam state of a steam generator when a high-temperature gas cooled reactor is started; performing power stage division on the full power range of the unit according to the characteristics of the reactor core and the steam state of the steam generator; according to the method, from starting of the high-temperature gas cooled reactor to full-power operation, the different power stages are analyzed according to the characteristics of the reactor core and the steam state of the steam generator, different control measurements are adopted according to the characteristics of the different power stages, and the power of the reactor is automatically controlled until the power of the reactor is increased to a full-power set value. And full-power stage automatic control is realized, the operation pressure of an operator is reduced, and the risk of misoperation is reduced.

Description

Technical Field

[0001] The present invention relates to the technical field of automatic power control of high temperature gas-cooled reactors, and in particular to a method and system for automatic segmented control of high temperature gas-cooled reactor units. Background Art

[0002] The high-temperature gas-cooled reactor is a modular nuclear power unit that adopts a machine-follow-reacting operation mode. During operation, the unit controls key parameters such as feed water flow, helium flow, nuclear power, and steam temperature to control the unit at the required power level.

[0003] Since the high-temperature gas-cooled reactor uses spherical fuel elements and graphite as a moderator, it has a large negative temperature reactivity coefficient. The physical characteristics of its core are different from those of a pressurized water reactor. The main control means of the unit are different at different power levels, so different control methods need to be adopted in different control stages.

[0004] The steam generator of the high-temperature gas-cooled reactor adopts a vertical, direct-current spiral tube assembly structure. The feed water is heated by the steam generator and becomes superheated steam. Therefore, during the startup phase of the unit, the secondary loop medium in the steam generator tube needs to transition from a water entity state to a superheated steam state. The two-phase flow control in the middle is the control difficulty of the unit startup.

[0005] Due to the small heat storage capacity of the steam generator, the helium flow rate, hot helium temperature, feed water flow rate and feed water temperature have a rapid and obvious impact on the steam generator. Therefore, how to adopt different control strategies in different control stages has become an urgent problem to be solved. Summary of the invention

[0006] In view of this, the present invention provides a staged fully automatic control method and system for a high temperature gas-cooled reactor unit to solve the problem of how to adopt different control strategies in different control stages.

[0007] In a first aspect, the present invention provides a method for fully automatic section control of a high temperature gas-cooled reactor unit, the method comprising:

[0008] When the HTGR is started up, the core characteristics and the steam status of the steam generator are monitored;

[0009] The full power range of the unit is divided into power stages according to the characteristics of the core and the steam state of the steam generator;

[0010] Each power stage is automatically controlled until the reactor power reaches the full power setting.

[0011] The present invention analyzes different power stages from the start-up of the high-temperature gas-cooled reactor to full-power operation according to the core characteristics and the steam state of the steam generator, adopts different control measurements according to the characteristics of different power stages, realizes automatic control of the full-power stage, reduces the operating pressure of the operator, and reduces the risk of misoperation.

[0012] In an optional embodiment, the control purpose is to reversely heat the first circuit through the second circuit, and the feed water flow and feed water temperature of the second circuit are controlled. The flow of the feed water pump is automatically controlled by the feed water flow control system, and the feed water temperature is automatically controlled by the heating system. When the steam generator outlet temperature reaches the first preset temperature and maintains the first preset time, the first control stage ends.

[0013] The present invention controls the feed water flow rate through a feed water flow control system and controls the feed water temperature through a heating system, so as to reversely heat the primary circuit through the secondary circuit, so that the primary circuit has a sufficient shutdown depth to prepare for the subsequent critical process.

[0014] In an optional embodiment, the power stage includes a second control stage, which automatically controls each power stage, including:

[0015] The control purpose is to make the reactor reach criticality, the control object is the power of the first circuit, the water flow rate of the second circuit is maintained unchanged, the helium flow rate of the first circuit is maintained unchanged, the control rods are automatically controlled by the rod control system, and the safety rod group is raised to the upper limit one by one through the power automatic control system, and then the compensation rods and the regulating rods are raised in turn. When the doubling period and the counting rate reach the critical conditions, the second control stage ends.

[0016] The present invention automatically controls the control rods through the rod control system and raises the rods through the power automatic control system to realize the control of the primary circuit power, thereby achieving the control purpose of the reactor reaching criticality.

[0017] In an optional implementation, the power stage includes a third control stage, which automatically controls each power stage, including:

[0018] The control purpose is to increase the reactor power and the steam generator outlet temperature, with the first circuit as the control object, maintaining the second circuit feed water flow and feed water temperature unchanged, maintaining the first circuit helium flow unchanged, automatically controlling the control rods through the rod control system, and alternately raising the compensation rods and the regulating rods through the power automatic control system. When the steam generator outlet temperature reaches the second preset temperature and is maintained for the second preset time, the third control stage ends.

[0019] The present invention automatically controls the control rods through the rod control system and raises the rods through the power automatic control system, so as to achieve the control purpose of increasing the reactor power and synchronously increasing the outlet temperature of the steam generator.

[0020] In an optional implementation, the power stage includes a fourth control stage, which automatically controls each power stage, including:

[0021] The control purpose is to adjust the helium flow rate to prepare for the transition of the two-phase flow. The rod control system alternately raises the compensation rod and the regulating rod, and the helium flow rate is automatically controlled by the helium flow controller until the outlet temperature of the steam generator is within the two-phase flow temperature range. The feed water flow rate is automatically controlled by the feed water flow controller until the helium flow rate and the feed water flow rate reach the target value;

[0022] With the control purpose of crossing the two-phase flow, the control rod is raised and the feed water flow rate is reduced until the steam generator outlet temperature is stably higher than the two-phase flow steam temperature, and the fourth control stage ends.

[0023] The present invention automatically lifts the rod through the rod control system, adjusts the helium flow rate through the helium flow controller, and adjusts the water flow rate through the water flow controller, so as to adjust the helium flow rate for preparation before the transition of the two-phase flow, and reduces the water flow rate by lifting the control rod to pass the two-phase flow.

[0024] In an optional implementation, the power stage includes a fifth control stage, which automatically controls each power stage, including:

[0025] The control purpose is to establish the end difference and increase the steam generator outlet temperature, and the primary circuit power is taken as the control object. The helium flow control system, the hot helium temperature control system, the steam temperature control system, and the feed water flow control system are coordinated to lift the control rod. When the steam generator outlet temperature reaches the third preset temperature and maintains the third preset time, the fifth control stage ends.

[0026] The present invention coordinates a helium flow control system, a hot helium temperature control system, a steam temperature control system, and a feed water flow control system to establish an end difference and increase the outlet temperature of the steam generator.

[0027] In an optional implementation, the power stage includes a sixth control stage, which automatically controls each power stage, including:

[0028] According to the unit steady-state characteristics table, increase and adjust the rod position, helium flow rate, and feed water flow rate until the power reaches the full power setting value, and the sixth control stage ends.

[0029] The present invention continuously improves and adjusts the rod position, helium flow rate, and water supply flow rate through coordinated control to achieve the purpose of increasing the power to the full power setting value.

[0030] In a second aspect, the present invention provides a high temperature gas-cooled reactor unit segmented fully automatic control system, the system comprising:

[0031] A monitoring module, used to monitor the characteristics of the core and the steam state of the steam generator when the high temperature gas-cooled reactor is started;

[0032] A stage division module is used to divide the full power range of the unit into power stages according to the characteristics of the core and the steam state of the steam generator;

[0033] The control module is used to automatically control each power stage until the reactor power rises to the full power setting value.

[0034] In a third aspect, the present invention provides a computer device, comprising: a memory and a processor, the memory and the processor are communicatively connected to each other, the memory stores computer instructions, and the processor executes the method for fully automatic control of a high-temperature gas-cooled reactor unit in section according to the first aspect or any corresponding embodiment thereof by executing the computer instructions.

[0035] In a fourth aspect, the present invention provides a computer-readable storage medium having computer instructions stored thereon, the computer instructions being used to enable a computer to execute the method for fully automatic control of a high-temperature gas-cooled reactor unit in a segmented manner according to the first aspect or any corresponding embodiment thereof. BRIEF DESCRIPTION OF THE DRAWINGS

[0036] In order to more clearly illustrate the specific implementation methods of the present invention or the technical solutions in the prior art, the drawings required for use in the specific implementation methods or the description of the prior art will be briefly introduced below. Obviously, the drawings described below are some implementation methods of the present invention. For ordinary technicians in this field, other drawings can be obtained based on these drawings without paying creative work.

[0037] Figure 1 is a schematic flow chart of a method for fully automatic section control of a high temperature gas-cooled reactor unit according to an embodiment of the present invention;

[0038] Figure 2 is a schematic diagram of a fully automatic control process of a high temperature gas-cooled reactor unit according to an embodiment of the present invention;

[0039] Figure 3 is a structural block diagram of a segmented fully automatic control system for a high temperature gas-cooled reactor unit according to an embodiment of the present invention;

[0040] Figure 4 It is a schematic diagram of the hardware structure of a computer device according to an embodiment of the present invention. DETAILED DESCRIPTION

[0041] In order to make the purpose, technical solution and advantages of the embodiments of the present invention clearer, the technical solution in the embodiments of the present invention will be clearly and completely described below in conjunction with the drawings in the embodiments of the present invention. Obviously, the described embodiments are part of the embodiments of the present invention, not all of the embodiments. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without creative work are within the scope of protection of the present invention.

[0042] The power operating range of the reactor module of the high temperature gas-cooled reactor is between 0-250MW, and each reactor module is equipped with a complete set of control systems. In order to achieve full-automatic control of the full power stage, during the process of reactor power increase, the embodiment of the present invention provides a high temperature gas-cooled reactor unit segmented full-automatic control method, which divides the full power range of the unit into stages according to the characteristics of the core and the steam state of the steam generator, and implements different automatic control strategies for different power stages. The process of automatic power reduction is opposite to the process of power increase.

[0043] According to an embodiment of the present invention, an embodiment of a method for fully automatic control of sections of a high-temperature gas-cooled reactor unit is provided. It should be noted that the steps shown in the flowchart of the accompanying drawings can be executed in a computer system such as a set of computer executable instructions, and although a logical order is shown in the flowchart, in some cases, the steps shown or described can be executed in an order different from that shown here.

[0044] In this embodiment, a method for fully automatic control of a high temperature gas-cooled reactor unit is provided. Figure 1 is a flow chart of a method for fully automatic control of a high temperature gas-cooled reactor unit according to an embodiment of the present invention. Figure 1 As shown, the process includes the following steps:

[0045] Step S101, when the high temperature gas-cooled reactor is started, the characteristics of the reactor core and the steam state of the steam generator are monitored.

[0046] In the embodiment of the present invention, starting from the start-up of the high temperature gas-cooled reactor, during the process of increasing the reactor power, the characteristics of the core and the steam state of the steam generator are monitored to divide the full power range of the unit into stages.

[0047] Step S102, dividing the full power range of the unit into power stages according to the characteristics of the core and the steam state of the steam generator.

[0048] In an embodiment of the present invention, during the reactor power boosting process, the full power range of the unit is divided into power stages according to the characteristics of the core and the steam state of the steam generator, namely, the first control stage, the second control stage, the third control stage, the fourth control stage, the fifth control stage and the sixth control stage.

[0049] Step S103, automatically controlling each power stage until the reactor power reaches the full power setting value.

[0050] In the embodiment of the present invention, different automatic control strategies are adopted for different power stages until the reactor runs at full power and the automatic control ends.

[0051] The present embodiment provides a method for fully automatic staged control of a high-temperature gas-cooled reactor unit, from the start-up of the high-temperature gas-cooled reactor to full-power operation. Different power stages are analyzed according to the core characteristics and the steam state of the steam generator, and different control measurements are adopted according to the characteristics of different power stages to achieve automatic control of the full-power stage, reduce the operating pressure of the operator, and reduce the risk of misoperation.

[0052] In this embodiment, a method for fully automatic control of a high temperature gas-cooled reactor unit is provided, and the process includes the following steps:

[0053] Step S201, when the high temperature gas-cooled reactor is started, the characteristics of the reactor core and the steam state of the steam generator are monitored.

[0054] For details, please see Figure 1 Step S101 of the illustrated embodiment will not be described in detail here.

[0055] Step S202, dividing the full power range of the unit into power stages according to the characteristics of the core and the steam state of the steam generator.

[0056] For details, please see Figure 1 Step S102 of the illustrated embodiment will not be described in detail here.

[0057] Step S203, automatically controlling each power stage until the reactor power reaches the full power setting value.

[0058] Specifically, when the power stage is the first control stage, the above step S203 automatically controls each power stage including:

[0059] Step S2031, with the control purpose of reverse heating the first circuit through the second circuit, and the feed water flow and feed water temperature of the second circuit as the control objects, automatically controls the flow of the feed water pump through the feed water flow control system, and automatically controls the feed water temperature through the heating system. When the steam generator outlet temperature reaches the first preset temperature and maintains the first preset time, the first control stage ends.

[0060] In the embodiment of the present invention, the first control stage is the reactor startup, from the shutdown state to before criticality. The main control purpose of this stage is to reversely heat the first circuit through the second circuit so that the first circuit has a sufficient shutdown depth to prepare for the subsequent critical process.

[0061] The main control objects in this stage are the secondary feedwater flow and feedwater temperature. The secondary feedwater enters the steam generator in the form of water entity through the start-stop system. The feedwater flow rate is controlled by the feedwater flow control system to control the water transfer of the feedwater pump, so as to achieve a constant feedwater flow rate Q during the startup process. w1 The feed water flow rate is manually set by the operator, and the feed water temperature is automatically controlled near the required temperature T1 by starting the heating system. The primary helium flow rate is controlled at a constant value Q by the helium flow control system. He1 nearby.

[0062] When the water flow rate is stable at Q w1 When the feed water temperature is stable near T1, the steam temperature is maintained near T1, keeping the temperature of the steam generator at the current temperature for time t1, and the first control stage ends.

[0063] The feed water flow rate is controlled by the feed water flow control system, and the feed water temperature is controlled by the heating system, so that the primary circuit is heated by the secondary circuit, so that the primary circuit has sufficient shutdown depth to prepare for the subsequent critical process.

[0064] Specifically, when the power stage is the second control stage, the above step S203 automatically controls each power stage including:

[0065] Step S2032, with the control purpose of reaching the criticality of the reactor and the power of the first circuit as the control object, the water flow rate of the second circuit is maintained unchanged, the helium flow rate of the first circuit is maintained unchanged, the control rods are automatically controlled by the rod control system, and the safety rod group is lifted to the upper limit one by one through the power automatic control system, and then the compensation rod and the adjustment rod are lifted in turn. When the doubling period and the counting rate reach the critical conditions, the second control stage ends.

[0066] In the embodiment of the present invention, the second control stage is when the reactor reaches criticality, and the main control object of this stage is the power of the primary circuit. In this stage, the feed water flow of the secondary circuit remains unchanged, that is, Q w2 =Q w1 , the feed water temperature remains unchanged, that is, the feed water temperature and steam temperature of this stage are the same as the feed water temperature and steam temperature of the previous stage, and the state of the second circuit remains unchanged. The helium flow rate of the first circuit remains unchanged Q He2 =Q He1, the reactor begins to reach critical operation by lifting the control rods. At this time, the rod control system automatically controls the control rods, and the power automatic control system lifts the reactor safety rod group to the upper limit one by one. When the safety rod group is lifted to the upper limit, the compensation rod and the regulating rod are lifted in turn. During the process, the rod lifting rate and the rod position of each rod lifting are constant, and the rod lifting interval is constant. The compensation rod and the regulating rod are continuously lifted in turn. The logic collects the multiplication cycle and the reactor internal source range nuclear measurement count rate in real time to determine whether the reactor is critical, and performs critical back-calculation at all times to give the critical extrapolated rod position in real time.

[0067] During the process of lifting the compensation rods and control rods, the doubling period and counting rate are monitored. When the doubling period begins to change stably, the operator can choose to modify the time interval for lifting the rods to slow down the increase rate of the counting rate and prevent the risk of instantaneous supercriticality.

[0068] After the doubling period and the counting rate are judged to have reached the critical conditions, it is declared critical, but the lifting of the compensation rod and the control rod is not stopped, and the second control stage is transferred to the third control stage.

[0069] The control rods are automatically controlled through the rod control system, and the rods are lifted through the power automatic control system to control the power of the primary circuit, thereby achieving the control purpose of the reactor reaching criticality.

[0070] Specifically, when the power stage is the third control stage, the above step S203 automatically controls each power stage including:

[0071] Step S2033, with the control purpose of increasing the reactor power and the steam generator outlet temperature, takes the first circuit as the control object, maintains the second circuit feed water flow and feed water temperature unchanged, keeps the first circuit helium flow unchanged, automatically controls the control rods through the rod control system, and alternately raises the compensation rods and the regulating rods through the power automatic control system. When the steam generator outlet temperature reaches the second preset temperature and is maintained for the second preset time, the third control stage ends.

[0072] In the embodiment of the present invention, the third control stage is to increase the power of the reactor into two-phase flow. The main control purpose of this stage is to increase the reactor power and simultaneously increase the steam generator outlet temperature. The main control object of this stage is the primary circuit.

[0073] During this stage, the feed water flow rate of the secondary circuit remains unchanged, the feed water temperature remains unchanged, and the state of the secondary circuit remains unchanged. The helium flow rate of the primary circuit remains unchanged, and the reactor performs power increase operations by lifting the control rods. When the reactor is critical, the rod lifting state is still maintained. At this time, the control rods are automatically controlled by the rod control system. The compensation rods and the regulating rods are lifted in turn through the power automatic control system. The rate of each rod lifting is constant V1, the distance of each rod lifting is constant S1, and the time interval between rod lifting is △T1. During the power increase process, the steam generator outlet temperature is monitored, and the rate of rod lifting is reversely corrected according to the steam generator heating rate requirement, that is, the control rod lifting interval △T1 is corrected each time. The reactor power increase rate is adjusted by automatically adjusting the △T1 time, and then the heating rate of the evaporator is controlled to ensure that the steam generator heating rate does not exceed the limit while the power is increased.

[0074] In order to ensure the control effect of the adjusting rod, when the adjusting rod position is lifted to 4000mm, the adjusting rod is no longer lifted, the adjusting rod keeps its position unchanged, and only the compensation rod is lifted.

[0075] When the reactor power is increased, the temperature of the evaporator is monitored during the heating process. When the temperature of the steam generator reaches the two-phase flow temperature, the control rod is stopped from being raised and the unit is stabilized on the platform. When the outlet temperature of the steam generator reaches the second preset temperature T2, it is maintained for a certain time t2 at this stage, and the third stage ends.

[0076] The control rods are automatically controlled through the rod control system, and the rods are raised through the power automatic control system to achieve the control purpose of increasing the reactor power and simultaneously increasing the steam generator outlet temperature.

[0077] Specifically, when the power stage is the fourth control stage, the above step S203 automatically controls each power stage including:

[0078] Step S2034a, with the purpose of adjusting the helium flow rate to prepare for the transition to two-phase flow, the rod control system alternately raises the compensation rod and the adjustment rod, and the helium flow rate is automatically controlled by the helium flow controller until the outlet temperature of the steam generator is within the two-phase flow temperature range, and the feed water flow rate is automatically controlled by the feed water flow controller until the helium flow rate and the feed water flow rate reach the target value.

[0079] Step S2034b, with the purpose of crossing the two-phase flow, lift the control rod and reduce the feed water flow until the steam generator outlet temperature is stably higher than the two-phase flow steam temperature, and the fourth control stage ends.

[0080] In the embodiment of the present invention, the fourth control stage is to pass the two-phase flow. The main task of this stage is to adjust the helium-water flow ratio, pass the two-phase flow and establish an appropriate steam generator outlet end difference.

[0081] This stage is divided into two control stages: the first stage is mainly to adjust the helium-water flow rate to prepare for the transition to two-phase flow, and the second stage is to pass the two-phase flow. The main control objects in this stage are helium flow rate, feed water flow rate, and control rods.

[0082] When crossing the two-phase flow, the heat of the first circuit can be increased while keeping the water flow rate unchanged, or the water flow rate of the second circuit can be reduced while keeping the heat of the first circuit unchanged, or the heat of the first circuit can be increased while reducing the flow rate of the second circuit. Among them, increasing the heat of the first circuit while reducing the flow rate of the second circuit can achieve crossing the two-phase flow. Among them, increasing the heat of the first circuit while reducing the flow rate of the second circuit is the fastest way to cross the two-phase flow.

[0083] After the transition of the two flows, the hot helium temperature is related to the helium flow rate. At the same power level, the lower the helium flow rate, the higher the hot helium temperature, and vice versa. A higher hot helium temperature is conducive to establishing the end difference of the steam generator and is more convenient for controlling the steam outlet temperature.

[0084] During the transition of two-phase flow, larger helium flow rate and water flow rate are conducive to the rapid transition of the two-phase flow and the stability of the transition.

[0085] In combination with the above three factors, the helium-water flow ratio needs to be adjusted before transitioning to two-phase flow.

[0086] In the first small stage, the helium flow rate is kept constant, the feed water flow rate of the second circuit is kept constant, and the power of the first circuit is increased by lifting the control rod (usually the compensation rod, at this time the regulating rod has reached the 4000 position and remains unchanged). At this time, the control rod is automatically controlled by the rod control system, and the compensation rod and the regulating rod are lifted in turn by the rod control system. The rate of each rod lifting is constant V1, the distance of each rod lifting is constant S1, and the time interval between rod lifting is △T1.

[0087] During the process, the changes in the outlet temperature of the steam generator are monitored at all times. When the outlet temperature of the steam generator fluctuates around the two-phase flow temperature, the control rod lifting is stopped.

[0088] After the control rod is stopped, the adjustment of helium flow and feed water flow begins. By setting the set value characteristic table of helium flow and feed water flow, the helium flow controller and feed water flow controller begin to control the helium flow and feed water flow for adjustment, gradually increase the helium flow and feed water flow to the target value, and enter the second small stage.

[0089] The main purpose of the second small stage is to cross the two-phase flow and establish the steam generator end difference after the transition.

[0090] Resume the control rod lifting action, each time the rate of the rod is constant V1, each time the distance of the rod is constant S1, and the time interval between the rod lifting is △T1. Synchronously start to reduce the feed water flow rate, and monitor the changes in the outlet temperature of the steam generator at all times during the process. When the outlet temperature of the steam generator begins to be higher than the two-phase flow temperature, stop reducing the feed water flow rate and keep lifting the control rod.

[0091] Continue to lift the control rods and increase the reactor power. Monitor the temperature of the evaporator during the heating process. When the steam generator outlet temperature is stably higher than a certain value of the two-phase flow steam temperature, stop lifting the control rods and the fourth stage ends.

[0092] The rod control system automatically lifts the rod, the helium flow is adjusted by the helium flow controller, and the water flow is adjusted by the water flow controller to prepare for the transition of the two-phase flow. The control rod is lifted and the water flow is reduced to cross the two-phase flow.

[0093] Specifically, when the power stage is the fifth control stage, the above step S203 automatically controls each power stage including:

[0094] Step S2035, with the purpose of establishing the end difference and raising the steam generator outlet temperature, with the power of one circuit as the control object, coordinate the helium flow control system, the hot helium temperature control system, the steam temperature control system, and the feed water flow control system, raise the control rod, and when the steam generator outlet temperature reaches the third preset temperature and maintains the third preset time, the fifth control stage ends.

[0095] In the embodiment of the present invention, the fifth control stage is when the steam temperature reaches the 450°C platform. The main control purpose of this stage is to establish the terminal difference and increase the steam generator outlet temperature. The main control object of this stage is the primary circuit power.

[0096] During this stage, the coordinated control stage is entered. During this stage, the unit's helium flow control system, hot helium temperature control system, steam temperature control system, and feed water flow control system are put into use to improve the unit's overall power level and power increase rate through coordinated control.

[0097] The nuclear power is increased by lifting the control rod (compensation rod) while keeping the feed water flow unchanged, slowly reducing the helium flow through the characteristic table, and slowly increasing the hot helium temperature and steam temperature. During the process, the steam generator outlet temperature and hot helium temperature are monitored, the steam generator heating rate is calculated synchronously, and the power increase rate is corrected according to the heating rate limit.

[0098] When the compensating rod is lifted to the top of the pile, the compensating rod remains stationary and the adjusting rods are lifted in turn.

[0099] When the steam temperature reaches 450℃, the power increase is stopped and the evaporator outlet temperature is stabilized for a period of time t3. During the stabilization process, conventional island operations such as turbine run-up can be carried out, and the fifth stage ends.

[0100] By coordinating the helium flow control system, hot helium temperature control system, steam temperature control system, and feed water flow control system, an end difference is established to increase the steam generator outlet temperature.

[0101] Specifically, when the power stage is the sixth control stage, the above step S203 automatically controls each power stage including:

[0102] Step S2036, according to the unit steady-state characteristic table, the rod position, helium flow rate, and feed water flow rate are increased and adjusted until the power reaches the full power setting value, and the sixth control stage ends.

[0103] In an embodiment of the present invention, the sixth control stage is to increase the power to full power. In this stage, the nuclear power, hot helium temperature and steam temperature of the unit are continuously increased by coordinated control according to the steady-state characteristic table of the unit by continuously increasing and adjusting the rod position, helium flow rate and feed water flow rate. During the process, the outlet temperature of the steam generator is monitored, and the rate of power increase is appropriately adjusted according to the heating rate of the steam generator to ensure that the heating rate of the steam generator does not exceed the limit.

[0104] When the outlet temperature of the steam generator and the hot helium temperature reach the predetermined temperature, conventional island operations such as steam and steam generation can be carried out.

[0105] Continue to increase the power. When the power reaches the full power setting value, the automatic power increase process of the unit ends.

[0106] Through coordinated control, the rod position, helium flow rate and water flow rate are continuously improved to achieve the purpose of increasing the power to the full power setting value.

[0107] The segmented fully automatic control method of the high-temperature gas-cooled reactor unit provided in this embodiment realizes the fully automatic control of the high-temperature gas-cooled reactor, realizes one-key start during the unit startup process, reduces the operator's operating pressure, reduces the risk of misoperation, improves the automation level of the power plant, reduces the unit startup time, and improves the economic and safety benefits of the unit.

[0108] like Figure 2 As shown, Figure 2 It is a flow chart of the staged fully automatic control process of the high temperature gas-cooled reactor unit, which is divided into stage one (i.e. the first control stage), stage two (i.e. the second control stage), stage three (i.e. the third control stage), stage four (i.e. the fourth control stage), stage five (i.e. the fifth control stage), and stage six (i.e. the sixth control stage).

[0109] Phase 1: The reactor is started, the secondary circuit reversely heats the primary circuit, the feed water flow and temperature are controlled, the helium flow of the primary circuit remains unchanged, and when the steam generator outlet temperature reaches the first preset temperature T1 and maintains the first preset time t1, Phase 1 ends.

[0110] Stage 2: The reactor reaches criticality, the secondary circuit water flow remains unchanged, the primary circuit helium flow remains unchanged, the rod control system automatically lifts the rods, raising the safety rod group to the upper limit one by one, and then raising the compensation rods and regulating rods in turn at a constant speed. When the doubling period and counting rate reach critical conditions, Stage 2 ends.

[0111] Stage three: The reactor increases its power and enters two-phase flow. The secondary circuit feed water flow remains unchanged, the primary circuit helium flow remains unchanged, the rod control system automatically lifts the rods, and lifts the compensation rods and the regulating rods at a constant speed in turn. When the steam generator outlet temperature reaches the second preset temperature T2 and is maintained for the second preset time t2, stage three ends.

[0112] Stage 4: When passing through two-phase flow, the rod control system automatically lifts the rod, adjusts the helium flow and feed water flow, controls the rod to be lifted, and reduces the feed water flow simultaneously. When the steam generator outlet temperature is stably higher than the two-phase flow steam temperature, stage 4 ends.

[0113] Stage 5: When the steam temperature reaches the 450℃ platform, the coordinated control is switched to increase the nuclear power by lifting the compensation rod, while keeping the feedwater flow unchanged, reducing the helium flow through the characteristic table, lifting the control rod, and keeping the feedwater flow unchanged. Stage 5 ends when the steam generator outlet temperature reaches the third preset temperature T3 and maintains the third preset time t3.

[0114] Stage 6: Increase to full power, and continuously improve the rod position, helium flow rate, and water flow rate through steady-state characteristics until the power reaches the full power setting value, and stage 6 ends.

[0115] In this embodiment, a high temperature gas-cooled reactor unit section fully automatic control system is also provided, which is used to implement the above embodiments and preferred implementations, and will not be repeated hereafter. As used below, the term "module" can be a combination of software and / or hardware that implements a predetermined function. Although the system described in the following embodiments is preferably implemented in software, the implementation of hardware, or a combination of software and hardware, is also possible and conceivable.

[0116] This embodiment provides a high temperature gas-cooled reactor unit segmented fully automatic control system, such as Figure 3 As shown, including:

[0117] The monitoring module 301 is used to monitor the characteristics of the reactor core and the steam state of the steam generator when the high temperature gas-cooled reactor is started.

[0118] The stage division module 302 is used to divide the full power range of the unit into power stages according to the characteristics of the core and the steam state of the steam generator.

[0119] The control module 303 is used to automatically control each power stage until the reactor power reaches the full power setting value.

[0120] In some optional implementations, the control module 303 includes:

[0121] The first control unit is used for the purpose of reverse heating the first circuit through the second circuit, and the control objects are the feed water flow and feed water temperature of the second circuit. The flow of the feed water pump is automatically controlled by the feed water flow control system, and the feed water temperature is automatically controlled by the heating system. When the outlet temperature of the steam generator reaches the first preset temperature and is maintained for the first preset time, the first control stage ends.

[0122] In some optional implementations, the control module 303 includes:

[0123] The second control unit is used to control the reactor to reach criticality and the power of the first circuit as the control object. It maintains the water flow rate of the second circuit unchanged, keeps the helium flow rate of the first circuit unchanged, automatically controls the control rods through the rod control system, and raises the safety rod group to the upper limit position one by one through the power automatic control system, and then raises the compensation rod and the adjustment rod in turn. When the doubling period and the counting rate reach the critical conditions, the second control stage ends.

[0124] In some optional implementations, the control module 303 includes:

[0125] The third control unit is used to increase the reactor power and the steam generator outlet temperature for the control purpose, take the first circuit as the control object, maintain the second circuit feed water flow and feed water temperature unchanged, keep the first circuit helium flow unchanged, automatically control the control rods through the rod control system, and alternately raise the compensation rods and the regulating rods through the power automatic control system. When the steam generator outlet temperature reaches the second preset temperature and is maintained for the second preset time, the third control stage ends.

[0126] In some optional implementations, the control module 303 includes:

[0127] The fourth control unit is used for the control purpose of adjusting the helium flow rate to prepare for the transition to two-phase flow. The rod control system alternately raises the compensation rod and the regulating rod, and automatically controls the helium flow rate through the helium flow controller until the outlet temperature of the steam generator is within the two-phase flow temperature range. The feed water flow rate is automatically controlled through the feed water flow controller until the helium flow rate and the feed water flow rate reach the target value.

[0128] The fifth control unit is used to lift the control rod and reduce the feed water flow rate for the control purpose of crossing the two-phase flow until the steam generator outlet temperature is stably higher than the two-phase flow steam temperature, and the fourth control stage ends.

[0129] In some optional implementations, the control module 303 includes:

[0130] The sixth control unit is used to establish the end difference and increase the steam generator outlet temperature for the control purpose, take the primary circuit power as the control object, coordinate the helium flow control system, the hot helium temperature control system, the steam temperature control system, and the feed water flow control system, and lift the control rod. When the steam generator outlet temperature reaches the third preset temperature and maintains the third preset time, the fifth control stage ends.

[0131] In some optional implementations, the control module 303 includes:

[0132] The seventh control unit is used to increase and adjust the rod position, helium flow rate, and feed water flow rate according to the unit steady-state characteristic table until the power reaches the full power setting value, and the sixth control stage ends.

[0133] The further functional description of each of the above modules and units is the same as that of the above corresponding embodiments and will not be repeated here.

[0134] The high-temperature gas-cooled reactor unit segmented fully automatic control system in this embodiment is presented in the form of functional units, where the units refer to ASIC (Application Specific Integrated Circuit) circuits, processors and memories that execute one or more software or fixed programs, and / or other devices that can provide the above functions.

[0135] The embodiment of the present invention also provides a computer device having the above Figure 3 The high temperature gas-cooled reactor unit section fully automatic control system shown.

[0136] See also Figure 4 , Figure 4 is a schematic diagram of the structure of a computer device provided by an optional embodiment of the present invention, such as Figure 4As shown, the computer device includes: one or more processors 10, a memory 20, and interfaces for connecting various components, including high-speed interfaces and low-speed interfaces. Various components are connected to each other using different buses for communication, and can be installed on a common mainboard or installed in other ways as needed. The processor can process the instructions executed in the computer device, including instructions stored in or on the memory to display the graphical information of the GUI on an external input / output device (such as, a display device coupled to the interface). In some optional embodiments, if necessary, multiple processors and / or multiple buses can be used together with multiple memories and multiple memories. Similarly, multiple computer devices can be connected, and each device provides some necessary operations (for example, as a server array, a group of blade servers, or a multi-processor system). Figure 4 A processor 10 is taken as an example.

[0137] The processor 10 may be a central processing unit, a network processor or a combination thereof. The processor 10 may further include a hardware chip. The hardware chip may be a dedicated integrated circuit, a programmable logic device or a combination thereof. The programmable logic device may be a complex programmable logic device, a field programmable gate array, a general purpose array logic or any combination thereof.

[0138] The memory 20 stores instructions executable by at least one processor 10, so that at least one processor 10 executes the method shown in the above embodiment.

[0139] The memory 20 may include a program storage area and a data storage area, wherein the program storage area may store an operating system, an application required for at least one function; the data storage area may store data created according to the use of the computer device, etc. In addition, the memory 20 may include a high-speed random access memory, and may also include a non-transient memory, such as at least one disk storage device, a flash memory device, or other non-transient solid-state storage device. In some optional embodiments, the memory 20 may optionally include a memory remotely arranged relative to the processor 10, and these remote memories may be connected to the computer device via a network. Examples of the above-mentioned network include, but are not limited to, the Internet, an intranet, a local area network, a mobile communication network, and combinations thereof.

[0140] The memory 20 may include a volatile memory, such as a random access memory; the memory may also include a non-volatile memory, such as a flash memory, a hard disk or a solid state drive; the memory 20 may also include a combination of the above types of memory.

[0141] The computer device also includes an input device 30 and an output device 40. The processor 10, the memory 20, the input device 30 and the output device 40 may be connected via a bus or other means. Figure 4 The example of connecting through bus is taken in the following.

[0142] The input device 30 can receive input digital or character information and generate key signal input related to user settings and function control of the computer device, such as a touch screen, etc. The output device 40 can include a display device, etc.

[0143] The embodiment of the present invention also provides a computer-readable storage medium. The method according to the embodiment of the present invention can be implemented in hardware, firmware, or can be implemented as a computer code that can be recorded in a storage medium, or can be implemented as a computer code that is originally stored in a remote storage medium or a non-temporary machine-readable storage medium and will be stored in a local storage medium through a network download, so that the method described herein can be stored in such software processing on a storage medium using a general-purpose computer, a dedicated processor, or programmable or dedicated hardware. Among them, the storage medium can be a magnetic disk, an optical disk, a read-only storage memory, a random access memory, a flash memory, a hard disk or a solid-state hard disk, etc.; further, the storage medium can also include a combination of the above types of memories. It can be understood that a computer, a processor, a microprocessor controller, or programmable hardware includes a storage component that can store or receive software or computer code. When the software or computer code is accessed and executed by a computer, a processor, or hardware, the method shown in the above embodiment is implemented.

[0144] A part of the present invention may be applied as a computer program product, such as a computer program instruction, which, when executed by a computer, can call or provide the method and / or technical solution according to the present invention through the operation of the computer. Those skilled in the art should understand that the existence of the computer program instruction in a computer-readable medium includes, but is not limited to, a source file, an executable file, an installation package file, etc., and accordingly, the way in which the computer program instruction is executed by the computer includes, but is not limited to: the computer directly executes the instruction, or the computer compiles the instruction and then executes the corresponding compiled program, or the computer reads and executes the instruction, or the computer reads and installs the instruction and then executes the corresponding installed program. Here, the computer-readable medium may be any available computer-readable storage medium or communication medium accessible to the computer.

[0145] Although the embodiments of the present invention have been described in conjunction with the accompanying drawings, those skilled in the art may make various modifications and variations without departing from the spirit and scope of the present invention, and such modifications and variations are all within the scope of the present application.

Claims

1. A method for fully automatic control of high temperature gas-cooled reactor units, characterized in that: The method comprises: When the HTGR is started up, the core characteristics and the steam status of the steam generator are monitored; Dividing the full power range of the unit into power stages according to the characteristics of the core and the steam state of the steam generator; Each power stage is automatically controlled until the reactor power reaches the full power setting.

2. The method according to claim 1, characterized in that The power stage includes a first control stage, and the automatic control of each power stage includes: The control purpose is to reversely heat the first circuit through the second circuit, and the feed water flow and feed water temperature of the second circuit are the control objects. The flow of the feed water pump is automatically controlled by the feed water flow control system, and the feed water temperature is automatically controlled by the heating system. When the outlet temperature of the steam generator reaches the first preset temperature and maintains the first preset time, the first control stage ends.

3. The method according to claim 1, characterized in that The power stage includes a second control stage, and the automatic control of each power stage includes: The control purpose is to make the reactor reach criticality, the power of the first circuit is the control object, the water flow rate of the second circuit is maintained unchanged, the helium flow rate of the first circuit is maintained unchanged, the control rods are automatically controlled by the rod control system, and the safety rod group is raised to the upper limit one by one through the power automatic control system, and then the compensation rods and the regulating rods are raised in turn. When the doubling period and the counting rate reach the critical conditions, the second control stage ends.

4. The method according to claim 1, characterized in that: The power stage includes a third control stage, and the automatic control of each power stage includes: The control purpose is to increase the reactor power and the steam generator outlet temperature, with the first circuit as the control object, maintaining the second circuit feed water flow and feed water temperature unchanged, maintaining the first circuit helium flow unchanged, automatically controlling the control rods through the rod control system, and alternately raising the compensation rods and the regulating rods through the power automatic control system. When the steam generator outlet temperature reaches the second preset temperature and is maintained for the second preset time, the third control stage ends.

5. The method according to claim 1, characterized in that The power stage includes a fourth control stage, and the automatic control of each power stage includes: The control purpose is to adjust the helium flow rate to prepare for the transition of the two-phase flow. The rod control system alternately raises the compensation rod and the regulating rod, and the helium flow rate is automatically controlled by the helium flow controller until the outlet temperature of the steam generator is within the two-phase flow temperature range. The feed water flow rate is automatically controlled by the feed water flow controller until the helium flow rate and the feed water flow rate reach the target value; With the control purpose of crossing the two-phase flow, the control rod is raised and the feed water flow rate is reduced until the steam generator outlet temperature is stably higher than the two-phase flow steam temperature, and the fourth control stage ends.

6. The method according to claim 1, characterized in that The power stage includes a fifth control stage, and the automatic control of each power stage includes: The control purpose is to establish the end difference and increase the steam generator outlet temperature, and the primary circuit power is taken as the control object. The helium flow control system, the hot helium temperature control system, the steam temperature control system, and the feed water flow control system are coordinated to lift the control rod. When the steam generator outlet temperature reaches the third preset temperature and maintains the third preset time, the fifth control stage ends.

7. The method according to claim 1, characterized in that The power stage includes a sixth control stage, and the automatic control of each power stage includes: According to the unit steady-state characteristics table, increase and adjust the rod position, helium flow rate, and feed water flow rate until the power reaches the full power setting value, and the sixth control stage ends.

8. A high temperature gas-cooled reactor unit section automatic control system, characterized in that: The system comprises: A monitoring module, used to monitor the characteristics of the core and the steam state of the steam generator when the high temperature gas-cooled reactor is started; A stage division module, used for dividing the full power range of the unit into power stages according to the characteristics of the core and the steam state of the steam generator; The control module is used to automatically control each power stage until the reactor power rises to the full power setting value.

9. A computer device, characterized in that: include: A memory and a processor, wherein the memory and the processor are communicatively connected to each other, the memory stores computer instructions, and the processor executes the method for fully automatic control of a high-temperature gas-cooled reactor unit according to any one of claims 1 to 7 by executing the computer instructions.

10. A computer-readable storage medium, characterized in that: The computer-readable storage medium stores computer instructions, and the computer instructions are used to enable a computer to execute the high-temperature gas-cooled reactor unit segmented fully automatic control method according to any one of claims 1 to 7.

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